Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant
The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element...
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| Format: | Article |
| Language: | English |
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Wiley
2014-01-01
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| Series: | The Scientific World Journal |
| Online Access: | http://dx.doi.org/10.1155/2014/743470 |
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| author | Sang-Uk Han Dae-Gyun Ahn Myeong-Gon Lee Kwon-Hee Lee Seung-Ho Han |
| author_facet | Sang-Uk Han Dae-Gyun Ahn Myeong-Gon Lee Kwon-Hee Lee Seung-Ho Han |
| author_sort | Sang-Uk Han |
| collection | DOAJ |
| description | The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements. |
| format | Article |
| id | doaj-art-daf20952a6be4f08b591349b852add5c |
| institution | Kabale University |
| issn | 2356-6140 1537-744X |
| language | English |
| publishDate | 2014-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | The Scientific World Journal |
| spelling | doaj-art-daf20952a6be4f08b591349b852add5c2025-02-03T01:23:57ZengWileyThe Scientific World Journal2356-61401537-744X2014-01-01201410.1155/2014/743470743470Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power PlantSang-Uk Han0Dae-Gyun Ahn1Myeong-Gon Lee2Kwon-Hee Lee3Seung-Ho Han4Department of Mechanical Engineering, Dong-A University, Busan 604-714, Republic of KoreaDepartment of Mechanical Engineering, Dong-A University, Busan 604-714, Republic of KoreaDepartment of Mechanical Engineering, Dong-A University, Busan 604-714, Republic of KoreaDepartment of Mechanical Engineering, Dong-A University, Busan 604-714, Republic of KoreaDepartment of Mechanical Engineering, Dong-A University, Busan 604-714, Republic of KoreaThe structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements.http://dx.doi.org/10.1155/2014/743470 |
| spellingShingle | Sang-Uk Han Dae-Gyun Ahn Myeong-Gon Lee Kwon-Hee Lee Seung-Ho Han Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant The Scientific World Journal |
| title | Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant |
| title_full | Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant |
| title_fullStr | Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant |
| title_full_unstemmed | Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant |
| title_short | Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant |
| title_sort | structural safety analysis based on seismic service conditions for butterfly valves in a nuclear power plant |
| url | http://dx.doi.org/10.1155/2014/743470 |
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